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Thermal/Hydrological Modeling of the Radioactive Scrap and Waste Facility (RSWF) with the Tough2 (Transport of Unsaturated Groundwater and Heat) Code

  • D. W. Esh (a1) and R. W. Benedict (a1)

Abstract

Thermal/hydrological modeling of the Radioactive Scrap and Waste Facility (RSWF) has been completed with the TOUGH2 (Transport of Unsaturated Groundwater and Heat) Code.[1] The RSWF will be utilized as an interim storage facility for ceramic and metallic waste forms developed from the electrometallurgical treatment of spent nuclear fuel. The RSWF is an array of 1,350 carbon steel liners located at grade near Argonne National Laboratory-West on the Idaho National Engineering Laboratory (INEL).

The primary driving force for this modeling research was to assess thermal capacity limits for RSWF liners so that heat generating materials can be safely stored. Maximum wasteform temperatures will be governed by both the amount of heat the system can dissipate and the orientation and characteristics of the wasteform. The focus of this report is on the amount of heat the interim storage system can safely dissipate. The effect of the temporal variation of soil moisture on the performance of the RSWF is assessed. The facility was analyzed to determine the maximum allowable thermal loading of the RSWF liners.

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References

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1. Pruess, K., “TOUGH2-A General Purpose Numerical Simulator for Multiphase Fluid and Heat Flow,” LBL-29400, Lawrence Berkeley Laboratory, Berkeley, CA (1991).
2. Notz, K. J., “Characteristics of Potential Repository Wastes,” Department of Energy, Washington, DC, Proceedings International Conference for High-Level Radioactive Waste Management, Las Vegas, NV, April 1990.
3. Moridis, G. and K., Pruess, “Flow and Transport Simulations Using T2CG1, A Package of Conjugate Gradient Solvers for the TOUGH2 Family of Codes,” LBL-36235, Lawrence Berkeley Laboratory, Berkeley, CA (1995).
4. Moridis, G. and K., Pruess, “TOUGH Simulations of Updegraff s Set of Fluid and Heat Flow Problems,” LBL-32611, Lawrence Berkeley Laboratory, Berkeley, CA (1992).
5. Childs, K. W., “HEATING 7.2 User's Manual,” ORNL/TM-12262, Oak Ridge National Laboratory, Oak Ridge, TN (1993).
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7. Martian, P. and Magnuson, S. O., “A Simulation Study of Infiltration Into Surficial Sediments at the Subsurface Disposal Area, Idaho National Engineering Laboratory,” EGG-WM-11250, EG&G Idaho, Idaho Falls, ID (1994).
8. Magnuson, S. O. and Sundrop, A. J., “A Modeling Study of Contaminant Transport Resulting From Flooding of Pit 9 at the Radioactive Waste Management Complex, Idaho National Engineering Laboratory,” EGG-EEL-10498, EG&G Idaho, Idaho Falls, ID (1992).
9. Pruess, K., “TOUGH User's Guide,” LBL-20700, Lawrence Berkeley Laboratory, Berkeley, CA (1987).
10. Milly, P. C. D., “Moisture and Heat Transport in Hysteretic, Inhomogeneous Porous Media: A Matric-Head Based Formulation and a Numerical Model,” Water Resources Research, 18, 3, 489498, 1982.10.1029/WR018i003p00489
11. Leverett, M. C., “Capillary Behavior in Porous Solids,” AIME Trans., 142, 152, 1941.10.2118/941152-G
12. Clarksean, R. L., Personal Communication, Argonne National Laboratory, Idaho Falls, ID (1994).
13. ”Standard Test Method for Determination of Water (Moisture) Content of Soil By Direct Heating Method,” ASTM D 4959–89, American Society for Testing and Materials, Philadelphia, PA (1989).

Thermal/Hydrological Modeling of the Radioactive Scrap and Waste Facility (RSWF) with the Tough2 (Transport of Unsaturated Groundwater and Heat) Code

  • D. W. Esh (a1) and R. W. Benedict (a1)

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